ML20114B529
| ML20114B529 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/30/1992 |
| From: | Miller D, Odell A, Ryan M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CCN-92-14104, NUDOCS 9208280324 | |
| Download: ML20114B529 (16) | |
Text
{{#Wiki_filter:. . _ _ . . _ - . _ _ _ _ . CCN 92-14104 PIIILADELPHIA ELECTRIC COAIPANY
, re PEACH BOTTOM A10MIC POWER STATION
# R.D.1, Box 208 g
- Delta, Pennsylvania 17314 l D_
nvu aantwm n mi a or i scu n sci (7171 456-7014 j D B M*ller, Jr. August 24, 1992 Vee Presnient Docket Nos.: 50-277 50-278 i U.S. Nuclear Regulatory Commission Attention: Document Control Desk l Mail Station P1 137 Washington, DC 20555
Subject:
Semi-annual Effluent Release Report No. 33 i January 1,1992 through June 30,1992 Peach Bottom Atomic Power Station - Units No. 2 and No. 3 3 Gentlemen: i Enclosed are two (2) copies of the Semi-annual Effluent Release Report No. 33, January 1,1992 through June 30,1992 for Peach Bottom Atomic Power Station - Units No. 2 and No. 3. This report is being submittad in compliance with 10 CFR 50.36a (a)(2) and the Technical a Specifications of Operating Licenses DPR-44 and DPR-56, and to fulfill the requirements of Regulatory Guide 10.1. , Sincerely, b1b ??Dgx tE n i G DBM/ /DPL/MJB:aus Enclosures cc: R. A. Burricelli, Public Service Electric & Gas T. M. Gerusky, Commonwealth of Pennsylvania J. J. Lyash, USNRC Senior Resident inspector, PBAPS R. McLean, State of Maryland T. T. Martin, Administrator, Region I, USNRC H. C. Schwemm, Atlantic Electric C. D. Schaefer, Delmarva Power INPO Records Center 280022 (# 9208280324 920630 PDR ADOCK 0S000277 R PDR
PEACH BOTTOM ATOMIC POWER STATION Unit Numbers 2 and 3 Docket Numbers 50-277 and 50 278 SEMI-ANNUAL EFFLUENT RELEASE REPORT NO. 33 JANUARY 1,1992 THROUGH JUNE 30,1992 Submitted to The United States Nuclear Regulatory Commission Pursuant to Facility Operating Licenses DPR44 and DPR-56
. v e
Table of Contents Section Page
- 1. Introduction j ll. Tatyps 1 A. Gaseous Etfluents Summation of All Releases 2
- 18. Gaseous Effluents for Release Po!nt Main Stack 3 1 C. Gaseous Effluents for Release Point -
Unit 2 and Unit 3 Roof Vents 5 2A. Liquid Effluents Summation of All Releases 7
- 28. Llquid Effluents 8 111. Classes of Solid Radioactive Wac19 Shipments 10 IV. Attachments A. Supplemental Information jg TEcfinical Concurrences: (for accuracy of information)
- b. g Senior Engineer Radwaste i/
h Senior Chemist
l i 1 1 , 1, INTRODUCTION ! l i I 4 in accordance with the Unique Reporting Requirements of Technical Specification 0.9.2h
- (2) applicable during the reporting period, this report summarizes the T.ffluent Release Data for Peach Bottom 40mic Power Station Units 2 and 3 for the period January 1 through June
! 30,1992. The notations E and E- are used to denote positive and negative exponents to the ) base 10, respectively. J
- The release of radiortive materials during the reporting period was within the Technical
! Specification limits. Th6,e were no changes made to the Off-Site Dose Calculation Manual ' l (ODCM) during the reporting period. There was one unplanned release of liquid radioactive materialinto the plant normal waste drains which communicate with the site storm drains (PBAPS LER 2-92-06). 1 i s i I
\
i i l i i i 4 l I ;
EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPOR T (1/1N2 - 630S2) Table 1 A Page 1 of 1 Gascous Effluents - Summation of All Releases Quarter Quarter Est. Error Units 1 j 2 Total % A. Fission & activation gases b p__ _1._T_ot_al release _..__ _ _ _ _ _ . _ _ . _ . , . . _ _ _ __Ci . __1_.05 E. _3 2.55 E_3__ 18.8
- 2. Average release rate forperiod_ _ _ g CiAcc__ _ 1.34 E2 3.28E2 18.8
- 3. Gamma Air Dose Millitad 2.89 E-2 3.33E-2 18.8
._ ___ ... Percent of Technical Specification % 2J19E- 1 3.33E- 1 18.8
- 4. Beta Air Dose Millirad 2.47E-2 3.25E-2 18.R Percent of Technical Snecification % 1.24 E- 1 1.63E- 1 18.8 B. lodines
_ _ _ 1. Totaligdine-131 . _ _ _ _ ._ _ _ _ , _. _Ci _ 1.66E-3 5.07E-3 22.9
- 2. Average release rate @r pgriod ._ . . _ _ . . _____._gCi/sce 2.11 E-4 _6.52 E- 4 _ . _22.9_
[. _ 3. Critical _ Organ dose Millirem 7.93E-3 _'. 00E -2 22.9 L.._ _ _ Percent of Technical Specification % }_ 5.293 - 2 1.33 E.- 1_ 22.9 C. Particulates E PHticuhiiessith li;ilf;Uds~j:Tfaiefihiiii8 ~ ~ ~~~-~ ' ~ ~ ~ '
~ ~ ~ ~ ~ ~ ~ ~
days _(includes Alpha and_ Strontium 89- 90)______._ _ _ _ Ci _ _1.4 3 E -- 3_ _1.27 E .__ 22 9
- 2. Average release rate for period pCiAcc 1.82 E-4 1.63E-4 22.9
_ 3. Average Grgsj Alpha Rad _ioactivity_.___ __ _ Ci _ t 4.93 E- b 3.91 E-6 22.9 D. Tritium
- 1. Total release Ci 8.87E0 1.10E1 23.5 L_._. 2. Average release rate for period pCiAcc 1.13E0 1.41 E0 23.5 2
EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPORT (1/lN2 - 6/30S2) Ts hic ill Page 1 of 2 Gascous Effluents For Release Point - Main Stack Continuous Mode
~~ liaiiMode Quartctl Quarter Quarter Quarter Nuclides_ Released __ _
_ _ . _ _ _ Units _j 1 2 1 2
- 1. Fission gases Krypton - 85M Ci 2.82 E1 1.50E2 0.00E 0 0.00E 0
___KTTP11n-87 _ Krypton - di _._ Ci _ . _ _ _3.36El _M6El 0.00E 0 0.00E 0 Ci 2.55E0 1.01 E2 0.00E 0 0.00E 0 Xenon - 133 Ci _ _ _ . . 5.30E2 . 1.49E3 0.00E 0 0.00E 0
. __ Xe npp - 133.1_ ___ . _ _ ___,_.___._ . ._ _ CL _ _ 2,31EL ,_ 1.11 E2 0.00E 0 0.00E 0 Xenon - 13X .
Ci 2.41 El 6.18E1 0.00E 0 0.00E 0 Xenon - 133M Ci 1.35El 9.44 LO 0.00E 0 0.00E 0 _ U_nidenlific_d_ ._______ __ _Ci_ OJX)E O 0.00E 0 _0]K)E O_ 01X)E O g ._ Tota _l for_ P_eriod _ _ _ _ _ _ ________1. _ Ci __ 9.34E2 _ 2.41_E3_ . 0.00E 0 __ 0.00E 0 l 2.lodines Ci _._10$90 2.131. _ __. _.__ _ _. _ _ _._ ] _ 6.68 E-4 3.46t!-3 0.00E 0 0.00E 0 lodine 133_ _. Ci _ . i 3.76E- 3 2.38 E-3 0.00E i 0.00E 0 lodine - 135 Ci 4.60E-3 3.12 E-3 0.00E 0 0.00E 0 Total for Period _ _ _ _ j _ Ci _ _ 9.03E-3 8.96E _3_ 0.00E 0 0.00E 0 3.Particulates St rontium - 89 - _ _ __j _ Ci
.-.._7-
_ 6.88E-4 4.76E-4 0.00E 0 01X)E 0 Strontium - 90 Ci 2.27E-6 1.32 E-6 0.00E 0 0.00E 0 Strontium - 91 . Ci 7.10E--4 6.78 E-4 0.00E 0 0!)0E 0
._ Ceslu!n _134 _ _ _ _ _ _ , _
Ci __ 0.00E 0_ _0.00E O 0.00E O OIX)E O _ Cesium _137 _ _ _ _ ,_ _ _ j Ci 6.79E-6 5.68E-6 0.00E 0 0.00E 0 Cesium - 138 Ci 1.62 E-2 2.23E-2 0.00E O 0.00E 0 Barium - .39 Ci 5.72 E-3 6A7E-3 OJX)E 0 0.00E 0 Barium - 140 Ci 5.85E-4 4.36 5 - 4 0.00E 0 0.00E 0 Lanthanum - 140 Ci 3.80E-4 2.69E-4 0.00E 0 0.00E 0
. _ _ _Co ba_lt - 5_7_ _ ._ _._ ___. I Ci DJX)E 0 0.00E 0 0.00E 0 0.00E 0 Cobalt - 58 ! Ci L 0.00E 0 0110E 0_ 0.00E 0 0.00E 0, 3
s
. -- ..- - -- -......-. - - _. - - -.- . --.=. ._ - -..._---- .
4 EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPORT (1/IN2 - 6/30N2) > Tabic til Page 2 of 2 l 4 Gascous Effluents For Release Point - Main Stacit I j Continuous Mode Batch Mode 1 I Quarter Quarter Quarter 'Ousrter Nuclides Released Units 1 2 1 2
, Cobalt - 60 Ci 0.00E O 0.00E O 0.00E O 0.00E O ,
; Zine - 65 Cl 0.00E 0 OJ)0E O 0.00E O 0.00E O {
Yttrium - 91_M Ci 6.04 E-3 1.19E-2 _ 0.00E O 0.00E 0 l lodine - 133 _ Ci 5.45E-6 1.45 E-5 0.00E 0 0.00E 0 l' _ Copper - 64 _Ci 0.00E O 0.00E O 0.00E O 0.00E O i Rubidium - 88 Cl 0.00E O 0110E O 0.00E 0 0.00E O i Manganese - 54 _ _ _ _ _ Ci 0110E 0 0.00E 0 0.00E 0 0.00E 0 Strontium - 92 Cl OJX)E 0 0.00E 0 OJX)E 0 0.00E 0 i Zirconium - 97 Ci 0.00E 0 1.74 E-5 0.00E 0 0.00E 0 , Technetium - 99m Ci 0.00E O 1.50E-6 0110E 0 0.00E O ! Molybdenum - 99 Ci 01)0E 0 1.00E-6 0.00E 0 ' O.00E 0 Totel for Period Ci 3.03E-2 4.26E-2 0.00E 0 0.00E 0 1 I I I t I l 4
. - , . . ~ , . _ _ . _ , _ . . _ _ . . _ _ _ . , _ _ _ _ _ . - . _ . , , _ _ _ . . _ , . . . . _ - _ . _ . _ . _ _ . , _ . . , _ _ _ . _ . - - , _ . , _ , _ _
EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPORT (1/192 - 6/3092) Tabic IC Page 1 of 2 Gascous Effluents For Release Point - Unit 2 & Unit 3 Roof Vents Continuous Mode Batch Mode - h Quarter Quarter Quarter Quarter Nuclides Released Units 1 2 1 2
- 1. Fission gases I
Krypt <m - 85M Ci 0.00E 0 0.00E 0 0.00E 0 0.00E 0 Krypton - 87 Ci _ 0.00E0 0.00E 0 0.00E 0_ 0.00E 0 _._K Jypton - R8 __
,_ __ _ _Gi 0.00E0 0.00E 0 _0.00E 0 0.00E 0 Xenop, J33 __ _
Ci _ 4.20E0 1.82E1 _ 0.00E 0 _ 0.00E 0
._ Xenon - 135 Ci 8.72E0 1.30El 0.00E 0 0.00E 0 Xenon - 135M Ci 0.00E 0 5.72E0 0.00E 0 0.00E 0 Xenon - 138 Ci 0.00E 0 0.00E 0 0.00E 0 0.00E 0
.__ Unidentified _ _ , _ _
I Ci 1.07E2 _ 1.11 E2 0.00E 0 0.00E 0
._ Total for Pcriod _ _ _ _ _ _ _
Cl 1.20E2 1.48E2_ 0.00E O 0.00E O 2.lodines lodine - 131 Ci 9.93E-4 1.61 E- 3 0.00E 0 0.00E 0 lodine - 133 _ ,_ Ci 8.51 E-3 9.95E-3 0.00E 0 0.00E 0
._ _ lodine - 135 .___
Ci 0.00E 0 0.00E 0 0.00E 0 0.00E 0 Total for Period Ci 9.50E-3 1.16E-2 0.00E 0 0.00E 0 3,Particulates Strontium - 89 Ci 1.45E-4 8.68E-5 0.00E 0 0.00E 0 Strontium - 9') Ci 3.01 E-6 4.09E-6 0.00E 0 0.00E O Strontium - 91 Ci 0.00E 0 0.00E O 0.00E 0 0.00E 0 Cesium - 134 Ci .. 0.00E O 0.00E O 0.00E O 0.00E O Cesium - 137 Ci 0.00E 0 3.32 E-5 0.00E O 0.00E O Cesium - 138 ._ Ci 4.33E-3 9.35 E-3 0.00E O 0.00E 0 _Ba!pm i - 139 _ Ci 8.36E-4 4.15 E- 4. 0.00E 0 0.00E 0 __ Barium - 140 _ Ci 0.00E 0 0.00E 0 0.00E 0 0.00E 0 Lmthanum - 140 Ci 0.00E 0 0.00E 0 0.00E 0 0.00E 0 Cobalt - 57 Ci 0.00E 0 OiXTE0 0.00E 0 0.00E 0 Cobalt - 58 __ _ Ci 0.00E O 0.00E O 0.00E O - 0.00E O Cobalt - 60 Ci O.00E 0 0.ME 0_ _ 0.00E 0 0.00E 0 5
[
. EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPORT (1/1/92 - 6/30/12)
Table 1C Page 2 of 2 Gascous Effluents l'or Release Point - Unit 2 & Unit 3 Roof Vents _ Continuous Mode llatch Mode Quarter Quarter Quarter Quarter Nuclides Released Units 1 2 1 2 Zine - 65 Ci 0.00 EO 0.00E0 0.00 EO 0.00 EO _ Yttrium - 91M _ C1 _ 0.00E O 0.00E0 0.00 EO 0.00 E0 , lodine - 133 _ _ Cl 1.45E-4 1.87E-5 0.00 EO 0.00 EO __ Copper - 64 Cl 0.00E0 0.00 EO 0.00 E0 0.00E0_ Rubidium - 88 Ci 0.00E0 0.00E0 0.00 EO 0.00 E0 Manganese - 54 _ Ci_ 0.00E0 0.00E0 0.00 EO 0.00 EO __Strontlum - 92 _ Ci _ _ 0.00E0 0.00E0 0.00 EO 0.00 E0 Cadmium - 109 Ci 0.00E O 2.18E-4 0.00 EO 0.00 EO __. Technetium - 99M ____ _ Ci 2.06E-5 0.00E0 0.00 EO 0.00 E0 Molybdenum - 99 Cf 1.87E-5 0.00E0 000 EO 0.00 E0 Total for Pcriod Ci 5.50E-3 1.01 E-2 0.00 EO 0.00 E0 I 1 I 6
- j. .
j - i 4 EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPORT (1/1/92 - 6/30/92) a j Tahic 2A Page1of1 i Liquid Effluents - Summation of All Releases s t Quarter Quarter Est. Error Units 1 __2 Total % { _ .__ l A. Fission & activallon products F i ~~~~1 T6TiilieleTiqHi>TincIEdi g fiitismTriises, 4 alphaL __ __ Ci 4.30E-3 ,_JL 1 22.9 _ l __,
- 2. Average diluted concentration duringpeilod _,_
_gCi/ml _194E-10 2.89h-t [. 39_ l 3. Total Body Dose _ _ _ _ Millitem 8.53E-4 1.39E-3 22.9 i Percent of Technical Specification _ % 2.84 E-2 4.63E-2 22.9 _ 4. Maximally Exposed Organ Dosc - Child Bone Millirem _ 3.05 E-3 5.13E-3 22.9 l Percent of Technical Specincajion _____ % 3.05 8 - 2_ 5.13E-2 22.9 1 B. Tritium - l
- 1. Total telease Ci 5.84 E 0 1.97E0 15.0
- 2. Average diluted concentration during period pCl/mi 2.63E-7 1.73 E-7_ 15.0 C. Dissolved and entrained gases
- 1. Total release l Cl 1.0$E-2 4.80E-3 22.9 i 2. Average diluted concentration duringperiod pCi/ml 4.73E- 10 4.21E-10 22.9 l D. Oross alpha radioacthity
, _ l Total release - Ci 1.08E-4 4.15E-5 22.9
- 2. A.erage diluted concentration during period pCi/ml- 4.86E- 12 3.64E-12 22.9
( E. Volume of waste released (prior to dilution)
. liters 2.43E6 8.32E5 - 12.7 F. Volume of dilution water used during period liters 222E10- 1.14E10 10.9 l
! 7 i
EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPORT (1/IN2 - 6/3032) Table 2B Page 1 of 2 1.iquid Effluents i l Continuous Mode Batch Mode l Quarter Quarter Quarter Quarter ] Nuclides Released Units 1 2 1 2 Strontium - 89 Ci 0.00E 0 0.00E 0 4.64E-5 3.14 E-5 Strontium - 90 Ci 0.00E 0 0.00E 0 9.28E-6 8.26E-6 Alpha ___ _ _ Ci 0.00E O 0.00E O 1.08E-4 4.15E-5 Tritium , _ Ci 0.00E 0 0.00E 0 f.84E 0 1.97E0 Phosphoru3 - 32 _ Ci 0.00E 0 _ 0.00E 0 1.28E-3 1.15E-3 Iron - 55 Ci 0.00E 0 0.00E 0 2.14 E-3 7.10E-4 _ Xenon - 131M Ci 0.00E 0 0.00E 0 0.00E 0 0.00E 0 Xenon - 133 Ci 0.00E 0 0.00E O 2.14 E-3 1.38E-3 i X mon - 133M Ci 0.00E O 0.00E 0 0.00E 0 0.00E 0 Xenon - 135 Ci 0.00E 0 0.00E 0 8.33E-3 3.41 E-3 Xenon - 135M Ci 0.00E 0 0.00E 0 7.12E-5 1.05E-5 [ Krypton - 85M _ Ci 0.00E 0 0.00E 0 0.00E 0 000E 0 Krypton - 87 _ Ci 0.00E 0 0.00E 0_ 0.00E 0 0.00E 0
._ Krypton - 88 Ci 0.00E 0 0.00E 0 0.00E 0 0.00E 0 Manganese - 54 Ci 0.00E 0 0.00E 0 0.00E 0 0.00E 0 Cesium - 134 Ci 0.00E 0 0.00E 0 2.59E-5 0.00E 0 Cesium - 137 _ _
Ci 0.00E 0 0.00E 0 2.21E-5 1.69E-6 Cesium - 138 Ci 0.00E 0 0.00E 0 0.00E 0 0.00E0 Zine - 65 Ci 0.00E 0 0.00E 0 0.00E 0 0.00E 0 Sodium - 24 Ci 0.00E 0 0.00E 0 0.00E 0 0.00E 0
.._ Cobalt - 58 __
Ci 0.00E 0 0.00E 0 0.00E 0 0.00E 0 Cobalt - 60 Ci 0.00E 0 0.00E 0 1.19E-5 0.00E 0 lodine - 131 Ci 0.00E 0 0.00E 0 0.00E 0 4.21 E-8 _ lodinc - 133 __ Ci 0.00E 0 0.00E 0 0.00E 0 3.95E-7 lodine - 135 Ci 0.00E 0 0.00E 0 0.00E 0 1.05E-6 Molybdenum - 99 Ci 0.00E 0 0.00E 0 0.00E 0 0.00E0 Barium - 140 Ci 0.00E 0 0.00E O 0.00E 0 0.00E0 _ Neptunium - 239 __ Ci 0.00E O 0.00E O 0.00E O 0.00E0 [- Chromium - 51 _ Ci 0.00E 0 0.00E 0 6.59E-4 1.25E-3 8 _ . ~ . _ . . - . _ . . - _ - . . - . . _ , . - . . - ~ , _ _ , ._
EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPORT (1/1/92 - 6/3092) Tabic 211 Page 2 of 2 Liquid Effluents _-._.._.._7_ Quarter Quarter Quarter Quarter Nuclides Released Units 1 2 1 2 _-_Yttr_ium - 91 M Ci 0.f0E 0 ____-._.__.-_-{ ' 0JX)E 0 0.00E 0 0.00E 0 _ . St rontium_ _91__ _ _ _ _ _ Ci 0.00E 0 0.00E 0 _ 0.00E 0 1.58E-7 Antimony - 122 Ci 0.00E 0 0.00E 0 0.00E 0 l 0.00E 0 _ _ Tellurium - 132 _ _ . . _ _ _ _ _ _ Ci 0.00E 0 0.00E 0 0.00E 0 0.00E 0
. Ni.obium - 95 . _ . . - -
Ci 0.0060 0.00E O 7.68E-6 0.00E O j r_ __ l Cadmium - 109 ! Ci 0.00E O 0.00E O 0.00E O 0.00E O l Ce 2m - 136 Ci 0.00E O 0.00E O 0.00E O 0.00E O Antimony - 124 Ci 0.00E O 0.00E 0 0.00E O 0.00E O Iron - 59 Ci 01)0E 0 0.00E O 0.00E O 0.00F 3
... Tellurium - 12_9M___ Ci 0.00E O 0.00E O 0.00E O 0/CEO
.. Tellurium 131M ._ _
_ _ _ . __ . _ Ci _ ,_. 0.00E O { OJX)F 0 _ 0.00E 0J 000E O a Zi rconiu m - 95_ -.. _. ._ __. ._ - _ . _._ _Ci . __ _._ .... OJK)E 0 _OJX)E 0 OJ)0E 0 0.00E 0 Strontium - 92 l Ci 03X)E 0 0.00E 0 01)0E 0 1.44 E-5 _. Cerium : 141 _ __. _.__ . _ _ _ _ _ _ ____ Ci _ 0.00E O _0.00E 0 OJX)E O 0.00E 0 __ Total for Period _(above)_ Ci 0.01E 0 1.98E0 0.00EO L 5.85E0 9
EFFLUENT & WASTE DISPOSAL SEMI- ANNUAL REPORT (1/192 - 6/.4092) PEACil BOTTOM UNITS 2 & 3 JANUARY 1,1992 TO JUNE 30,1992 CLASSES OF SOLID RADIOACTIVE WASTE SillPMENTS m____- __ Total # of Waste Description Volume Volume Total Principal
. Shipments (source of wastcL Containcr/ Type (cubic It.)_. _(cubic ft.)_ _ Curic_ Radionuclides Class A 29 Dewatered Resin lilC/ Type A Cask 202.1 5860.9 1.45E + 02 Cs- 137, Zn-65, Cs - 134, Co-00, Cr-51 38 DAW Afetal Drum /STC variabic (') 1408.8 4.09E + 00 Co-60, Cs- 137, hicial Box /STC Fe-55, Cr-51, Zn-65 21 DAW hietr.1 Drum /STC variable (") 81.8 3.84 E-01 Co-60, Cs- 137, Metai BoVSTC Fe-55, Cs- 1.34, Ni-63 Class B 5 Dewatered Resin 111C/ Type A Cask 202.1 1010.5 1.28E + 02 Cs- 137, Cs- 134, Co-60, Zn-65, Ni-63 1 Dewatered Resin HIC / Type B Cask 132.4 132.4 8.64 E+ 02 Cr-51, Zn -65, Co- 60, Cs-137, Co-58 Class C 1 Irradiated Metal Steel Lincr/ 57.4 $7.4 2.23E+04 Fe-55, Co-60, Type B Cask Mn- 54, Ni-63, C-14 k
Totals i 95 8551.8 234E+04 NOTES:
'- Indicates actual total PECo radwaste shipped from Quadrex, after volume reduction, to the burial site.
"- Indicates actual total PECo radwaste shipped from SEG, after volume reduction, to the burial site, 10 j
ATTACHMENT A SUPFLEMENT INF.ORMATION Facil.1y: Peach Bottom Units 2 & 3 Licenses: DPR-44 DPR-56
- 1. Regulat_ory_ Limits {Teghnical.Specifjcation Lirnits)
A. Noble _ Gases;
- 1. 5 500 mRomNr - total body -
' instantaneous' limits 5 3000 mRomNr - skin Tech. Spec. 3.8.C.1.a
- 2. 5 10 mrad - air gamma -
quarterly air dose limits 5 20 mrad - air beta Tech. Spec. 3.8.C.2.a
- 3. s 20 mrad - air gamma -
yearly air dose limits s 40 mF.ad - air beta Tech. Sperc. 3.8.C.2.b B. lo. dines,T.ritium,farticulates_with_Hialf Life > 8 days;
- 1. 51500 mrem /Yr - any organ -
'ir.stantaneous' limits (inhalation path) Tech. Spec. 3.8.C.1.b
- 2. s 15 mrem - any organ -
quarterly dose limits Tech. 3pec. 3.8.C 3.a
- 3. 5 30 mrem - any organ -
yearly dose limits Tech. Spec. 3.8.C.O.b C Liqu.id Effluents
- 1. ConcentraJon s 10 CFR 20 -
' instantaneous' limits Appendix B, Table 11, Col. 2 Tech. Spec. 3.8.B.1
- 2. s 3.0 mrem - total bodv -
quarterly dose limits s 10 mrem - any organ Tech. Spec. 3.8.B.2.a
- 3. < 6.0 mrem - total body -
yearly case limits
< 20 mrem - any organ Tech. Spec. 3.8.B.E.b
- 2. Magimum he:missibje, Concentrations; MPCs are not used to calculate permissible release rates and concentrations for gaseous releases.
The MPCs specified in 10 CFR 20, Appendix B, Table it, Column 2. for identified nuclides are used to calculate permissible release rates and concentrations for liquid release per Peach Bottom Technical Specification 3.8.B.1. I!
. . . . _ __ _ _ _ ___ _ _ - - - - -- -J
ATTACHMENT A (continued)
- 3. Average En_ergy; Not Applicable
- 4. Measu.rements and Approxima_tions_of Tptal Radioactivity; A. Eissi.on and Activation Gases; The method used is the Nuclear Data 6700 Counting System
- Gas Marinel!! ~
B. lodine; The method used is the Nuclear Data 6700 Counting System
- Charcoal Cartridge -
C. . Particulate _sj The method used is the Nuclear Data 6700 CountinD System
- Air Particulate Sample, (47mm and 57mm filters) -
D. Liquid Effluents; The method used is the Nucicar Data 6700 Counting System and the Radwasto Uquid Dischargo Pre-Release Method with a liter marinelli.
- 5. By;h Releases; A. Wald:
OTR 1 OI!L2 Number of batch releases: 38 17 Total time for batch releases (minutes): 8680 3446 Maximum time perio. for batch release (minues): 370 450 Average time oeriod for batch release (minates): 241 203 Minimum time period for batch release (minutes): 60 38 Dilution flow (liters): 2.22E10 1.14E10 B. Gaseou.s; Not applicable. 12
4 i . ATTACHMENT A (continued)
- 6. Abnormal Roleases; A. Liquid; PBAPS ER 2-92-06 Event Descriptien - On April 7,1992 an observed leak on 196' elevation in the Turbine Building was reported to the Control Room. A Floor Foreman was dispatdied to invectigate the leak. The Floor Foreman reported back that the leak was on a one inch vent line and could not be isolated during current plant conditions. The leaking vent he was connected to a six inch condensate line, in approximately 30 minutes from the reported leak, the one inch vent line weld broke and Flant shutdown commenced in accordance with approved station prococures.
The weld failure allowed condensate water to enter the normal waste drains which com-municate with site storm drains. Immediately after condensate water was identified as entering the normat waste drains, surveys were performed of the site storm drains. - Samples obtained from the storm drains indicated that no activ;;y was present.
!! was estimated that approximately 20 gallons of condensate water was released to the normal waste drains. A liquid sample was obtained from the condensata line wtilch is assumed to be representative of the effluent released. The sample results indicated the activity released was well below the limits specified in Technical Specifications.
Analysis of Release - The representative sample obtained was analyzed for all the r parameters of a r,'.dioactive effluent release. The results were then calculated based on conservative release conditions (i.e., minimum dilution and maximum release rate), , The Doc.e contribut;ons and isotope quantities were added to the Semi- Annual ' Effluent Repon for the applicable reporting period. D. Gaseous; PBAPS GR 2-92-07 Event Description - During March 1992, surveillances were performed to gather the weekly Particulate Fitters from the Unit 2 & 3 Vent Stack Exhaust and the Main Stack. Tha Filtem were composited for the month and sent to the chemistry analysis con-tractor, Teledyne Isotopes Laboratory, for analysis. On April 7,1992 the contractor contacted PECo Chemistry and informed thc m that the Particulate Filters were not in , their possession and they had no locord of receiving them. Corrective Actions - Future samples sont to the contractor will be put in a more conspicuous container to minimize the possibility of being discarded. The Particulate Filters will be cut in half prior to off-site shipment to the contractor. Upon receipt of the contractor analysls, the results will be multiplied by 2. Sample Results for March 1992 - In accordance with the corrective actions of PBAPS GR 2-92-07, a detailed evaluation of plant operating conditions for the period of the lost samples was conducted. As a result, the sample analysis results from the r.1onth of April 1992 were determined to provido the best estirnate of the lost samples. Also to provide some lovel of conservatism, all sarapie results were multiplied by a factor of 2. Post Event Observatior . - Since the implementations of the corrective actions of PBAPS GR 2-92-07,io similar evetits have occurred. i 13 _____- -}}